US20100123107A1 - Method and composition for moderated nuclear fuel - Google Patents
Method and composition for moderated nuclear fuel Download PDFInfo
- Publication number
- US20100123107A1 US20100123107A1 US12/274,578 US27457808A US2010123107A1 US 20100123107 A1 US20100123107 A1 US 20100123107A1 US 27457808 A US27457808 A US 27457808A US 2010123107 A1 US2010123107 A1 US 2010123107A1
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- United States
- Prior art keywords
- nuclear fuel
- neutron moderator
- hafnium
- zirconium
- recited
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- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 54
- 239000000203 mixture Substances 0.000 title claims abstract description 28
- 238000000034 method Methods 0.000 title claims description 11
- 239000000446 fuel Substances 0.000 claims abstract description 30
- 229910052735 hafnium Inorganic materials 0.000 claims abstract description 22
- VBJZVLUMGGDVMO-UHFFFAOYSA-N hafnium atom Chemical compound [Hf] VBJZVLUMGGDVMO-UHFFFAOYSA-N 0.000 claims abstract description 22
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 claims abstract description 21
- 229910052726 zirconium Inorganic materials 0.000 claims abstract description 21
- -1 hafnium hydride Chemical compound 0.000 claims description 19
- QSGNKXDSTRDWKA-UHFFFAOYSA-N zirconium dihydride Chemical compound [ZrH2] QSGNKXDSTRDWKA-UHFFFAOYSA-N 0.000 claims description 17
- 229910000568 zirconium hydride Inorganic materials 0.000 claims description 17
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 claims description 16
- 229910052739 hydrogen Inorganic materials 0.000 claims description 16
- 239000001257 hydrogen Substances 0.000 claims description 16
- 239000003085 diluting agent Substances 0.000 claims description 11
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 claims description 8
- 238000004845 hydriding Methods 0.000 claims description 6
- 229910052742 iron Inorganic materials 0.000 claims description 4
- 229910052702 rhenium Inorganic materials 0.000 claims description 4
- WUAPFZMCVAUBPE-UHFFFAOYSA-N rhenium atom Chemical compound [Re] WUAPFZMCVAUBPE-UHFFFAOYSA-N 0.000 claims description 4
- WFKWXMTUELFFGS-UHFFFAOYSA-N tungsten Chemical compound [W] WFKWXMTUELFFGS-UHFFFAOYSA-N 0.000 claims description 4
- 229910052721 tungsten Inorganic materials 0.000 claims description 4
- 239000010937 tungsten Substances 0.000 claims description 4
- 229910052695 Americium Inorganic materials 0.000 claims description 3
- 229910052685 Curium Inorganic materials 0.000 claims description 3
- 229910052781 Neptunium Inorganic materials 0.000 claims description 3
- 229910052778 Plutonium Inorganic materials 0.000 claims description 3
- 229910052770 Uranium Inorganic materials 0.000 claims description 3
- LXQXZNRPTYVCNG-UHFFFAOYSA-N americium atom Chemical compound [Am] LXQXZNRPTYVCNG-UHFFFAOYSA-N 0.000 claims description 3
- LFNLGNPSGWYGGD-UHFFFAOYSA-N neptunium atom Chemical compound [Np] LFNLGNPSGWYGGD-UHFFFAOYSA-N 0.000 claims description 3
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 claims description 3
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 claims description 3
- 230000009257 reactivity Effects 0.000 description 13
- 239000002826 coolant Substances 0.000 description 10
- 239000011800 void material Substances 0.000 description 4
- 238000010521 absorption reaction Methods 0.000 description 3
- 238000010248 power generation Methods 0.000 description 3
- 238000001228 spectrum Methods 0.000 description 3
- 230000008901 benefit Effects 0.000 description 2
- 150000004678 hydrides Chemical class 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 229910052768 actinide Inorganic materials 0.000 description 1
- 150000001255 actinides Chemical class 0.000 description 1
- 238000007865 diluting Methods 0.000 description 1
- 238000010790 dilution Methods 0.000 description 1
- 239000012895 dilution Substances 0.000 description 1
- 230000008030 elimination Effects 0.000 description 1
- 238000003379 elimination reaction Methods 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 229910001385 heavy metal Inorganic materials 0.000 description 1
- 229910001338 liquidmetal Inorganic materials 0.000 description 1
- 239000011159 matrix material Substances 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 229910044991 metal oxide Inorganic materials 0.000 description 1
- 150000004706 metal oxides Chemical class 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000003071 parasitic effect Effects 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000009467 reduction Effects 0.000 description 1
- 238000005245 sintering Methods 0.000 description 1
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/62—Ceramic fuel
- G21C3/623—Oxide fuels
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/12—Moderator or core structure; Selection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Definitions
- This disclosure relates to a moderated nuclear fuel composition for providing a desired prompt negative reactivity coefficient.
- Nuclear fuels used in fast reactors as breeders, actinide burners, or power reactors typically exhibit relatively small or negligible negative prompt coefficients of reactivity.
- One reason for this is a lack of Doppler broadening in such fuels.
- neutron energies in a typical nuclear fuel of a fast reactor are much greater than nuclei resonance ranges where Doppler broadening occurs.
- Neutron energies may be several hundred keV and Doppler broadening may occur primarily below 25 keV.
- the prompt coefficient of reactivity of the nuclear fuel is weak or negligible.
- voiding in the surrounding coolant removes parasitic neutron absorption and causes a positive coolant void coefficient, which is generally an undesirable condition.
- An example nuclear fuel composition includes a transuranic fuel and a neutron moderator mixed with transuranic fuel.
- the neutron moderator includes at least one of hafnium or zirconium.
- an example nuclear fuel composition includes 8 wt %-45 wt % of the transuranic fuel and a balance being the neutron moderator.
- the transuranic fuel is selected from uranium, plutonium, americium, neptunium, curium and combinations thereof, and the neutron moderator includes hafnium hydride and zirconium hydride.
- An example method of moderating a nuclear fuel includes mixing a transuranic fuel with a neutron moderator that includes hafnium to thereby provide a nuclear fuel composition where the hydrogen in the hafnium hydride moderates neutrons of the transuranic fuel.
- FIG. 1 schematically illustrates an example nuclear reactor system having a nuclear fuel that includes a transuranic fuel and a neutron moderator.
- FIG. 2 is a cross-section showing a mixture of the transuranic fuel and the neutron moderator of the nuclear fuel.
- FIG. 1 schematically illustrates selected portions of an example nuclear reactor system 10 for power generation.
- the nuclear reactor system 10 includes a reactor vessel 12 that is submerged within a coolant 14 (e.g., water, liquid metal, etc.) contained within a containment vessel 16 .
- the reactor vessel 12 includes a core 18 including nuclear fuel 20 that is used to heat the coolant 14 in a known manner.
- the coolant 14 circulates through the reactor vessel 12 , as indicated by the flow arrows, to a heat exchanger 22 that transfers heat from the coolant 14 to another working fluid, such as water.
- a heat exchanger 22 that transfers heat from the coolant 14 to another working fluid, such as water.
- Such an arrangement may be used to produce steam for downstream power generation.
- the nuclear fuel 20 includes a composition for providing a strong negative prompt coefficient of reactivity and a reduction or elimination of a positive coolant void coefficient of the coolant 14 .
- the nuclear fuel 20 includes a transuranic fuel 24 and a neutron moderator 26 mixed with the transuranic fuel.
- the transuranic fuel 24 is dispersed through a matrix of the neutron moderator 26 .
- the transuranic fuel may be selected from uranium, plutonium, americium, neptunium, curium and combinations thereof.
- the neutron moderator 26 includes hafnium, zirconium, or combination thereof, which reduces a velocity of fast/high energy neutrons within the core 18 through sub-atomic collisions.
- Hafnium and zirconium have a low neutron energy resonance relative to the several hundred keV of the neutrons of the transuranic fuel 24 .
- the low resonance of the hafnium and/or zirconium in the neutron moderator 26 reduces the neutron energy spectrum of the nuclear fuel 20 .
- the hafnium and/or zirconium of the nuclear fuel 20 may be in the form of hydrides, such as hafnium hydride or zirconium hydride (e.g., HfH x or ZrH x , where x is the atomic ratio of hydrogen to heavy metal Hf and/or Zr).
- the hydrogen of the hydride provides neutron moderation by slowing the velocity of fast neutrons within the core 18 .
- the hydrogen is an effective moderator because hydrogen may reduce the velocity of a neutron in a single sub-atomic collision.
- the addition of the hafnium and/or zirconium with the hydrogen in the nuclear fuel 20 reduces the neutron energy spectrum of the nuclear fuel 20 from several hundred keV to a range that at least partially overlaps a Doppler broadening range below about 25 keV.
- the nuclear fuel 20 exhibits a strong negative prompt coefficient of reactivity.
- the phenomena of Doppler broadening is caused by an apparent broadening of the energy resonances of the hafnium due to thermal motion of nuclei.
- the negative prompt coefficient of reactivity of the nuclear fuel 20 also may limit or eliminate a positive coolant void coefficient. For instance, moderating the nuclear fuel 20 using the neutron moderator 26 may increase the negative prompt coefficient of reactivity sufficient enough to offset the positive coolant void coefficient.
- the neutron moderator 26 may include zirconium hydride and hafnium hydride. Similar to the hafnium, the zirconium has a low neutron energy resonance relative to the several hundred keV of the neutrons of the transuranic fuel 24 and thereby reduces the neutron energy spectrum of the nuclear fuel 20 . However, the hafnium is thought to have a different effectiveness than the zirconium in providing a prompt negative coefficient of reactivity. Thus, the ratio of hafnium to zirconium may be controlled in the composition of the nuclear fuel 20 to establish a desired negative prompt coefficient of reactivity.
- a total combined weight of the hafnium hydride and the zirconium hydride may include 1 wt % of the hafnium hydride and a balance of the zirconium hydride or as much as about 99 wt % of the hafnium hydride and 1 wt % of the zirconium hydride.
- the ratio of hafnium hydride to zirconium hydride may be 75/25, 50/50, 25/75, or other desired ratio, depending on a desired amount of prompt negative temperature coefficient of reactivity.
- the neutron moderator 26 may additionally include a neutron moderator diluent used to reduce the amount of the neutron moderator 26 .
- the neutron moderator diluent may be used to further control the reactivity of the nuclear fuel 20 by diluting the moderating effectiveness of the neutron moderator 26 .
- the neutron moderator diluent is selected from iron, tungsten, rhenium, or mixtures thereof.
- the amount of neutron moderator diluent may vary, depending upon the desired reactivity of the nuclear fuel 20 .
- the amount of the neutron moderator diluent may be anywhere from fractions of a weight percent of the nuclear fuel 20 up to weight percentages that are several times greater than the amount of hafnium hydride and/or zirconium hydride in the neutron moderator 26 , depending on a desired degree of dilution of the hafnium hydride and/or zirconium hydride.
- the transuranic fuel 24 , the hafnium, the zirconium, and optionally the neutron moderator diluent of the nuclear fuel 20 may be combined using any suitable technique.
- mixing techniques known for forming conventional nuclear fuels that include metal or metal oxide mixed with zirconium may be applied to form the example nuclear fuel 20 .
- the nuclear fuel 20 may be a mixture of powders of the transuranic fuel 24 and the neutron moderator 26 that are then sintered into a desired shape, such as a rod or pellet.
- the transuranic fuel 24 , the hafnium, and/or the zirconium of the neutron moderator 26 may be hydrided in a hydriding process (e.g., either before or after sintering).
- the nuclear fuel 20 may be exposed to gaseous hydrogen at an elevated temperature for a predetermined amount of time (i.e., hydriding parameters) to incorporate hydrogen into the nuclear fuel 20 .
- the hydriding parameters at least partially determine the concentration of the hydrogen in the nuclear fuel 20 , such as the hydrogen to hafnium or zirconium ratio of 1.6-1.7.
- hydriding parameters that are known for zirconium hydride may be used to produce the hafnium hydride.
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- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Ceramic Engineering (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Fuel Cell (AREA)
Abstract
Description
- This disclosure relates to a moderated nuclear fuel composition for providing a desired prompt negative reactivity coefficient.
- Nuclear fuels used in fast reactors as breeders, actinide burners, or power reactors typically exhibit relatively small or negligible negative prompt coefficients of reactivity. One reason for this is a lack of Doppler broadening in such fuels. For instance, neutron energies in a typical nuclear fuel of a fast reactor are much greater than nuclei resonance ranges where Doppler broadening occurs. Neutron energies may be several hundred keV and Doppler broadening may occur primarily below 25 keV. As a result, the prompt coefficient of reactivity of the nuclear fuel is weak or negligible. Additionally, voiding in the surrounding coolant removes parasitic neutron absorption and causes a positive coolant void coefficient, which is generally an undesirable condition.
- An example nuclear fuel composition includes a transuranic fuel and a neutron moderator mixed with transuranic fuel. The neutron moderator includes at least one of hafnium or zirconium.
- In another aspect, an example nuclear fuel composition includes 8 wt %-45 wt % of the transuranic fuel and a balance being the neutron moderator. The transuranic fuel is selected from uranium, plutonium, americium, neptunium, curium and combinations thereof, and the neutron moderator includes hafnium hydride and zirconium hydride.
- An example method of moderating a nuclear fuel includes mixing a transuranic fuel with a neutron moderator that includes hafnium to thereby provide a nuclear fuel composition where the hydrogen in the hafnium hydride moderates neutrons of the transuranic fuel.
- The various features and advantages of the disclosed examples will become apparent to those skilled in the art from the following detailed description. The drawings that accompany the detailed description can be briefly described as follows.
-
FIG. 1 schematically illustrates an example nuclear reactor system having a nuclear fuel that includes a transuranic fuel and a neutron moderator. -
FIG. 2 is a cross-section showing a mixture of the transuranic fuel and the neutron moderator of the nuclear fuel. -
FIG. 1 schematically illustrates selected portions of an examplenuclear reactor system 10 for power generation. However, it is to be understood that this disclosure is not limited to the arrangement of the examplenuclear reactor system 10 for power generation, and the concepts disclosed herein may be applied to other reactor systems that may be used for other purposes. In the illustrated example, thenuclear reactor system 10 includes areactor vessel 12 that is submerged within a coolant 14 (e.g., water, liquid metal, etc.) contained within acontainment vessel 16. Thereactor vessel 12 includes acore 18 includingnuclear fuel 20 that is used to heat thecoolant 14 in a known manner. For instance, thecoolant 14 circulates through thereactor vessel 12, as indicated by the flow arrows, to aheat exchanger 22 that transfers heat from thecoolant 14 to another working fluid, such as water. Such an arrangement may be used to produce steam for downstream power generation. - In the illustrated example, the
nuclear fuel 20 includes a composition for providing a strong negative prompt coefficient of reactivity and a reduction or elimination of a positive coolant void coefficient of thecoolant 14. As shown in a schematic cross-section of one of thenuclear fuel 20 inFIG. 2 , thenuclear fuel 20 includes atransuranic fuel 24 and aneutron moderator 26 mixed with the transuranic fuel. For instance, thetransuranic fuel 24 is dispersed through a matrix of theneutron moderator 26. The transuranic fuel may be selected from uranium, plutonium, americium, neptunium, curium and combinations thereof. Theneutron moderator 26 includes hafnium, zirconium, or combination thereof, which reduces a velocity of fast/high energy neutrons within thecore 18 through sub-atomic collisions. - Hafnium and zirconium have a low neutron energy resonance relative to the several hundred keV of the neutrons of the
transuranic fuel 24. Thus, the low resonance of the hafnium and/or zirconium in theneutron moderator 26 reduces the neutron energy spectrum of thenuclear fuel 20. - The hafnium and/or zirconium of the
nuclear fuel 20 may be in the form of hydrides, such as hafnium hydride or zirconium hydride (e.g., HfHx or ZrHx, where x is the atomic ratio of hydrogen to heavy metal Hf and/or Zr). The hydrogen of the hydride provides neutron moderation by slowing the velocity of fast neutrons within thecore 18. The hydrogen is an effective moderator because hydrogen may reduce the velocity of a neutron in a single sub-atomic collision. Thus, the addition of the hafnium and/or zirconium with the hydrogen in thenuclear fuel 20 reduces the neutron energy spectrum of thenuclear fuel 20 from several hundred keV to a range that at least partially overlaps a Doppler broadening range below about 25 keV. As a result of the Doppler broadening, thenuclear fuel 20 exhibits a strong negative prompt coefficient of reactivity. In one example, the phenomena of Doppler broadening is caused by an apparent broadening of the energy resonances of the hafnium due to thermal motion of nuclei. That is, stationary nuclei only absorb neutrons of certain resonance energies, whereas if the nucleus is moving away from the neutron or toward the neutron, the apparent velocity of the neutron with velocities greater or less than the original absorption energy to will now undergo resonance absorption. By reducing the velocity of the neutrons using theneutron moderator 26, a sufficient number of neutrons will have energies that will overlap the Doppler broadened resonance thereby providing a negative prompt coefficient of reactivity of thenuclear fuel 20. - The negative prompt coefficient of reactivity of the
nuclear fuel 20 also may limit or eliminate a positive coolant void coefficient. For instance, moderating thenuclear fuel 20 using theneutron moderator 26 may increase the negative prompt coefficient of reactivity sufficient enough to offset the positive coolant void coefficient. - In a further example, the
neutron moderator 26 may include zirconium hydride and hafnium hydride. Similar to the hafnium, the zirconium has a low neutron energy resonance relative to the several hundred keV of the neutrons of thetransuranic fuel 24 and thereby reduces the neutron energy spectrum of thenuclear fuel 20. However, the hafnium is thought to have a different effectiveness than the zirconium in providing a prompt negative coefficient of reactivity. Thus, the ratio of hafnium to zirconium may be controlled in the composition of thenuclear fuel 20 to establish a desired negative prompt coefficient of reactivity. For instance, a total combined weight of the hafnium hydride and the zirconium hydride may include 1 wt % of the hafnium hydride and a balance of the zirconium hydride or as much as about 99 wt % of the hafnium hydride and 1 wt % of the zirconium hydride. In other examples, the ratio of hafnium hydride to zirconium hydride may be 75/25, 50/50, 25/75, or other desired ratio, depending on a desired amount of prompt negative temperature coefficient of reactivity. - The
neutron moderator 26 may additionally include a neutron moderator diluent used to reduce the amount of theneutron moderator 26. The neutron moderator diluent may be used to further control the reactivity of thenuclear fuel 20 by diluting the moderating effectiveness of theneutron moderator 26. In a few examples, the neutron moderator diluent is selected from iron, tungsten, rhenium, or mixtures thereof. The amount of neutron moderator diluent may vary, depending upon the desired reactivity of thenuclear fuel 20. In a few examples, the amount of the neutron moderator diluent may be anywhere from fractions of a weight percent of thenuclear fuel 20 up to weight percentages that are several times greater than the amount of hafnium hydride and/or zirconium hydride in theneutron moderator 26, depending on a desired degree of dilution of the hafnium hydride and/or zirconium hydride. - The
transuranic fuel 24, the hafnium, the zirconium, and optionally the neutron moderator diluent of thenuclear fuel 20 may be combined using any suitable technique. For example, mixing techniques known for forming conventional nuclear fuels that include metal or metal oxide mixed with zirconium may be applied to form the examplenuclear fuel 20. In this regard, thenuclear fuel 20 may be a mixture of powders of thetransuranic fuel 24 and theneutron moderator 26 that are then sintered into a desired shape, such as a rod or pellet. - After combining, the
transuranic fuel 24, the hafnium, and/or the zirconium of theneutron moderator 26 may be hydrided in a hydriding process (e.g., either before or after sintering). For instance, thenuclear fuel 20 may be exposed to gaseous hydrogen at an elevated temperature for a predetermined amount of time (i.e., hydriding parameters) to incorporate hydrogen into thenuclear fuel 20. The hydriding parameters at least partially determine the concentration of the hydrogen in thenuclear fuel 20, such as the hydrogen to hafnium or zirconium ratio of 1.6-1.7. In this regard, hydriding parameters that are known for zirconium hydride may be used to produce the hafnium hydride. - Although a combination of features is shown in the illustrated examples, not all of them need to be combined to realize the benefits of various embodiments of this disclosure. In other words, a system designed according to an embodiment of this disclosure will not necessarily include all of the features shown in any one of the Figures or all of the portions schematically shown in the Figures. Moreover, selected features of one example embodiment may be combined with selected features of other example embodiments.
- The preceding description is exemplary rather than limiting in nature. Variations and modifications to the disclosed examples may become apparent to those skilled in the art that do not necessarily depart from the essence of this disclosure. The scope of legal protection given to this disclosure can only be determined by studying the following claims.
Claims (20)
Priority Applications (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US12/274,578 US8000431B2 (en) | 2008-11-20 | 2008-11-20 | Method and composition for moderated nuclear fuel |
| FR0957936A FR2938690B1 (en) | 2008-11-20 | 2009-11-10 | PROCESS AND COMPOSITION OF MODERN NUCLEAR FUEL |
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| Application Number | Priority Date | Filing Date | Title |
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| US12/274,578 US8000431B2 (en) | 2008-11-20 | 2008-11-20 | Method and composition for moderated nuclear fuel |
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| US20100123107A1 true US20100123107A1 (en) | 2010-05-20 |
| US8000431B2 US8000431B2 (en) | 2011-08-16 |
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| FR (1) | FR2938690B1 (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20130083878A1 (en) * | 2011-10-03 | 2013-04-04 | Mark Massie | Nuclear reactors and related methods and apparatus |
| WO2017184255A3 (en) * | 2016-02-26 | 2017-11-30 | Oklo, Inc. | Passive inherent reactivity coefficient control in nuclear reactors |
| US20240055145A1 (en) * | 2020-12-16 | 2024-02-15 | Tokamak Energy Ltd. | On the design of a composite hydride-metal to accommodate hydride decomposition |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| SE534031C2 (en) * | 2010-05-07 | 2011-04-05 | Westinghouse Electric Sweden | Control rod for a nuclear light water reactor |
| US11955249B2 (en) * | 2020-10-29 | 2024-04-09 | Westinghouse Electric Company Llc | Heat pipe having a wick between concentric inner and outer housings, for use in heat removal from a nuclear reactor core |
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| US20130083878A1 (en) * | 2011-10-03 | 2013-04-04 | Mark Massie | Nuclear reactors and related methods and apparatus |
| WO2017184255A3 (en) * | 2016-02-26 | 2017-11-30 | Oklo, Inc. | Passive inherent reactivity coefficient control in nuclear reactors |
| US10692611B2 (en) | 2016-02-26 | 2020-06-23 | Oklo, Inc. | Passive inherent reactivity coefficient control in nuclear reactors |
| US20240055145A1 (en) * | 2020-12-16 | 2024-02-15 | Tokamak Energy Ltd. | On the design of a composite hydride-metal to accommodate hydride decomposition |
Also Published As
| Publication number | Publication date |
|---|---|
| FR2938690B1 (en) | 2016-02-05 |
| US8000431B2 (en) | 2011-08-16 |
| FR2938690A1 (en) | 2010-05-21 |
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